ANS / Publications / Journals / Nuclear Science and Engineering

New Approach to Space-Dependent Kinetic Analysis by the Integral Kinetic Model

Hiroki Takezawa, Toru Obara

Nuclear Science and Engineering / Volume 171 / Number 1 / May 2012 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE09-59

Neutron Balance Analysis for Sustainability of Breed-and-Burn Reactors

Florent Heidet, Ehud Greenspan

Nuclear Science and Engineering / Volume 171 / Number 1 / May 2012 / Pages 13-31

Technical Paper / dx.doi.org/10.13182/NSE10-114

Development of a HEX-Z Partially Homogenized Benchmark Model for the FFTF Isothermal Physics Measurements

John D. Bess

Nuclear Science and Engineering / Volume 171 / Number 1 / May 2012 / Pages 32-40

Technical Paper / dx.doi.org/10.13182/NSE10-100

Heuristic Methods for Assigning Spent Nuclear Fuel Assemblies to Canisters for Final Disposal

Timo Ranta, Frank Cameron

Nuclear Science and Engineering / Volume 171 / Number 1 / May 2012 / Pages 41-51

Technical Paper / dx.doi.org/10.13182/NSE10-111

A Burnup-Dependent Isomeric Production Branching Ratio Treatment

W. Haeck, B. Cochet, L. Aguiar

Nuclear Science and Engineering / Volume 171 / Number 1 / May 2012 / Pages 52-68

Technical Paper / dx.doi.org/10.13182/NSE10-99

Reliability Models of Aging Passive Components Informed by Materials Degradation Metrics to Support Long-Term Reactor Operations

Stephen D. Unwin, Peter P. Lowry, Michael Y. Toyooka

Nuclear Science and Engineering / Volume 171 / Number 1 / May 2012 / Pages 69-77

Technical Paper / dx.doi.org/10.13182/NSE11-18

Measurement of Neutron-Induced Reaction Cross Sections in Zirconium Isotopes at Thermal, 2.45 MeV and 9.85 MeV Energies

P. M. Prajapati, S. Mukherjee, H. Naik, A. Goswami, S. V. Suryanarayana, S. C. Sharma, B. S. Shivashankar, V. K. Mulik, K. C. Jagdeesan, S. V. Thakre, S. Bisnoi, T. Patel, K. K. Rasheed, S. Ganesan

Nuclear Science and Engineering / Volume 171 / Number 1 / May 2012 / Pages 78-84

Technical Paper / dx.doi.org/10.13182/NSE11-02

Evaluations of Fission Chain Yields for ²³⁹Pu from Fission-Spectrum Neutrons

I. J. Thompson, Y. M. X. M. Dardenne, J. M. Kenneally, A. Robertson, L. E. Ahle, C. A. Hagmann, R. A. Henderson, D. Vogt, C.-Y. Wu, W. Younes

Nuclear Science and Engineering / Volume 171 / Number 2 / June 2012 / Pages 85-135

Technical Paper / dx.doi.org/10.13182/NSE10-101

Use of Zirconium-Based Moderators to Enhance Feedback Coefficients in a MOX-Fueled Sodium-Cooled Fast Reactor

Bruno Merk, Sören Kliem, Emil Fridman, Frank-Peter Weiss

Nuclear Science and Engineering / Volume 171 / Number 2 / June 2012 / Pages 136-149

Technical Paper / dx.doi.org/10.13182/NSE10-58

A Comparison of Pulsing Characteristics of the Oregon State University TRIGA Reactor with FLIP and LEU Fuel

W. R. Marcum, T. S. Palmer, B. G. Woods, S. T. Keller, S. R. Reese, M. R. Hartman

Nuclear Science and Engineering / Volume 171 / Number 2 / June 2012 / Pages 150-164

Technical Paper / dx.doi.org/10.13182/NSE11-25

Explicit Treatment of Thermal Motion in Continuous-Energy Monte Carlo Tracking Routines

Tuomas Viitanen, Jaakko Leppänen

Nuclear Science and Engineering / Volume 171 / Number 2 / June 2012 / Pages 165-173

Technical Paper / dx.doi.org/10.13182/NSE11-36

Development of Self-Interrogation Neutron Resonance Densitometry to Quantify the Fissile Content in PWR Spent LEU and MOX Assemblies

Adrienne M. LaFleur, William S. Charlton, Howard O. Menlove, Martyn T. Swinhoe

Nuclear Science and Engineering / Volume 171 / Number 3 / July 2012 / Pages 175-191

Technical Paper / dx.doi.org/10.13182/NSE11-40

Evaluation of ⁵⁴Fe(n, 2n) Cross Sections and Their Covariance Data Below 20 MeV

Jing Qian, Min Jia, Tingjin Liu

Nuclear Science and Engineering / Volume 171 / Number 3 / July 2012 / Pages 192-203

Technical Paper / dx.doi.org/10.13182/NSE10-93

Cross-Section Measurement of Thermal Neutron-Induced Fission on ²⁴³Cm

L. Popescu, J. Heyse, J. Wagemans, C. Wagemans

Nuclear Science and Engineering / Volume 171 / Number 3 / July 2012 / Pages 204-209

Technical Paper / dx.doi.org/10.13182/NSE11-65

Refining the Accuracy of Predicting Physics Parameters at Research Reactors due to the Limitations in the Energy Balance Method Using MCNP and the ENDF Evaluations

N. J. Peters, J. C. McKibben, K. Kutikkad, W. H. Miller

Nuclear Science and Engineering / Volume 171 / Number 3 / July 2012 / Pages 210-219

Technical Paper / dx.doi.org/10.13182/NSE10-71

An Orthonormally Weighted Standardized Time Series for the Error Estimation of Local Tallies in Monte Carlo Criticality Calculation

Taro Ueki

Nuclear Science and Engineering / Volume 171 / Number 3 / July 2012 / Pages 220-230

Technical Paper / dx.doi.org/10.13182/NSE11-35

Evaluation and Uncertainty Analysis of the KRITZ-2 Critical Benchmark Experiments

Ivan Kodeli, Luka Snoj

Nuclear Science and Engineering / Volume 171 / Number 3 / July 2012 / Pages 231-238

Technical Paper / dx.doi.org/10.13182/NSE11-62

On-the-Fly Doppler Broadening for Monte Carlo Codes

Gokhan Yesilyurt, William R. Martin, Forrest B. Brown

Nuclear Science and Engineering / Volume 171 / Number 3 / July 2012 / Pages 239-257

Technical Paper / dx.doi.org/10.13182/NSE11-67

Time-Fractional Telegrapher's Equation (P1) Approximation for the Transport Equation

Gilberto Espinosa-Paredes, Marco Antonio Polo-Labarrios

Nuclear Science and Engineering / Volume 171 / Number 3 / July 2012 / Pages 258-264

Technical Note / dx.doi.org/10.13182/NSE11-58